3701:1-38-01
Definitions.

(A)
As used in this chapter and all other
rules promulgated pursuant to Chapter 3748. of the Revised Code:

(1)
"A1" means the
maximum activity of special form radioactive material permitted in a type A
package. These values are listed in rule
3701:1-50-25 of the
Administrative Code, or may be derived in accordance with the procedure
prescribed in rule
3701:1-50-25 of the
Administrative Code.

(2)
"A2 " means the maximum activity of radioactive
material, other than special form, low specific activity and surface
contaminated object material, permitted in a type A package. These values are
listed in rule
3701:1-50-25 of the
Administrative Code, or may be derived in accordance with the procedure
prescribed in rule
3701:1-50-25 of the
Administrative Code.

(3)
"Absorbed
dose" means the energy imparted by ionizing radiation per unit mass of
irradiated material. The units of absorbed dose are the gray, or Gy, and the
rad.

(4)
"Accelerator or charged
particle accelerator" means any of a class of radiation generating equipment
designed to electronically accelerate atomic or sub-atomic particles for
subsequent bombardment of targets.

(5)
"Accelerator-produced radioactive
material" means any material made radioactive by a particle
accelerator.

(6)
"Activity" means
the rate of disintegration or transformation or decay of radioactive material.
The units of activity are the becquerel, or Bq, and the curie, or Ci.

(7)
"Address of use" means the building or
buildings that are identified on the license or registration and where the
source of radiation may be received, used, prepared, or stored, except for
temporary job sites.

(8)
"Administrative controls" means mechanisms used to protect health and minimize
damage to life and property through the use of written policies, procedures,
instructions, training, observation of work practices, and related compliance
audits.

(9)
"Administrative
monetary penalty" means a monetary penalty assessed by the director under
section 3748.05 of the Revised Code and
in compliance with rules adopted thereunder, to emphasize the need for lasting
remedial action and to deter future violations.

(11)
"Agreement
state" means any state with which the United States nuclear regulatory
commission or the atomic energy commission has entered into an effective
agreement under subsection 274B of the Atomic Energy Act. Non-agreement state
means any other state.

(12)
"Airborne radioactive material" means radioactive material dispersed in the air
in the form of dusts, fumes, particulates, mists, vapors, or gases.

(13)
"Airborne radioactivity area" means a
room, enclosure, or area in which airborne radioactive materials, composed
wholly or partly of licensed material, exist in concentrations:

(a)
In excess of the derived air
concentrations (DACs) specified in appendix C to rule
3701:1-38-12 of the
Administrative Code, or

(b)
To such
a degree that an individual present in the area without respiratory protective
equipment could exceed, during the hours an individual is present in a week, an
intake of 0.6 per cent of the annual limit on intake or twelve
DAC-hours.

(14)
"Air-purifying respirator" means a respirator with an air-purifying filter,
cartridge, or canister that removes specific air contaminants by passing
ambient air through the air-purifying element.

(15)
"ALARA" or "as low as is reasonably
achievable" means every reasonable effort to maintain exposures to radiation as
far below the dose limits as is practical consistent with the purpose for which
the licensed or registered activity is undertaken, taking into account the
state of technology, the economics of improvements in relation to benefits to
the public health and safety, and other societal and socioeconomic
considerations, and in relation to utilization of nuclear energy and licensed
materials and registered activities in the public interest.

(16)
"Alert" means events may occur, are in
progress, or have occurred that could lead to a release of radioactive material
but that the release is not expected to require a response by off-site response
organizations to protect persons off-site.

(17)
"Annual limit on intake" or "ALI" means
the derived limit for the amount of radioactive material taken into the body of
an adult worker by inhalation or ingestion in a year. ALI is the smaller value
of intake of a given radionuclide in a year by the reference man that would
result in a committed effective dose equivalent of 0.05 sievert (five rem) or a
committed dose equivalent of 0.5 sievert (fifty rem) to any individual organ or
tissue. ALI values for intake by ingestion and by inhalation of selected
radionuclides are given in appendix C to rule
3701:1-38-12 of the
Administrative Code.

(b)
Once per
year, at about the same time each year, plus or minus one month.

(19)
"Area of use" means a portion
of an address of use that has been set aside for the purpose of receiving,
preparing, using, or storing sources of radiation.

(20)
"Assigned protection factor" or "APF"
means the expected workplace level of respiratory protection that would be
provided by a properly functioning respirator or a class of respirators to
properly fitted and trained users. Operationally, the inhaled concentration can
be estimated by dividing the ambient airborne concentration by the
APF.

(21)
"Atmosphere-supplying
respirator" means a respirator that supplies the respirator user with breathing
air from a source independent of the ambient atmosphere, and includes supplied
air respirators, or SARs, and self-contained breathing apparatus, or SCBA,
units.

(22)
"Atomic energy
commission" or "AEC" means the federal agency created by the Atomic Energy Act
of 1954, as amended, and was the predecessor agency to the current United
States nuclear regulatory commission created by the Energy Reorganization Act
of 1974.

(23)
"Background
radiation" means radiation from cosmic sources; naturally occurring radioactive
materials, including radon, except as a decay product of source or special
nuclear material, and global fallout as it exists in the environment from the
testing of nuclear explosive devices or from past nuclear accidents such as
Chernobyl that contribute to background radiation and are not under the control
of the licensee. "Background radiation" does not include radiation from
radioactive materials regulated by the department.

(24)
"Becquerel" or "Bq" means the SI unit of
activity. One becquerel is equal to one disintegration per second.

(25)
"Bioassay" or "radiobioassay" means the
determination of kinds, quantities or concentrations, and, in some cases, the
locations of radioactive material in the human body, whether by direct
measurement, in vivo counting, or by analysis and evaluation of materials
excreted or removed from the human body.

(a)
Any radioactive material, except special
nuclear material, yielded in or made radioactive by exposure to the radiation
incident to the process of producing or utilizing special nuclear materials;
or

(b)
The tailings or wastes
produced by the extraction or concentration of uranium or thorium from any ore
processed primarily for its source material content, including discrete surface
wastes resulting from solution extraction processes. Underground ore bodies
depleted by such solution extraction do not constitute byproduct material
within the definition.

(27)
"Chelating agent" means a chemical
compound or mixture that enhances the removal of radioactive material from the
body, water or similar applications. Typical chelating agents include amine
polycarboxylic acids such as EDTA or DTPA; hydroxy-carboxylic acids; and
polycarboxylic acids such as citric acid, carbolic acid, and gluconic
acid.

(28)
"Chiropractor" means an
individual licensed by the state of Ohio to practice chiropractic medicine
pursuant to Chapter 4734. of the Revised Code.

(29)
"Class" or "lung class" or "inhalation
class" means a classification scheme for inhaled material according to its rate
of clearance from the pulmonary region of the lung. Materials are classified as
D, W, or Y, which applies to a range of clearance half-times: for class D,
days, of less than ten days, for class W, weeks, from ten to one hundred days,
and for class Y, years, of greater than one hundred days.

(30)
"Collective dose" means the sum of the
individual doses received in a given period of time by a specified population
from exposure to a specified source of radiation.

(31)
"Commencement of construction" means
taking any action defined
as "construction" or any other activity at the site of a facility subject to
the rules promulgated pursuant to Chapter 3748. of the Revised Code that has a
reasonable nexus to radiological health and safety.

(32)
"Committed dose equivalent" or
"HT,50 " means the dose equivalent to organs or tissues
of reference, T, that will be received from an intake of radioactive material
by an individual during the fifty year period following the intake.

(33)
"Committed effective dose equivalent" or
"HE,50 " means the sum of the products of the weighting
factors applicable to each of the body organs or tissues,
WT, that are irradiated and the committed dose
equivalent to each of these organs or tissues (HE, 50 =
WT HT,50).

(34)
"Consortium" means an association of
medical use licensees and a PET radionuclide production facility in the same
geographical area that jointly own or share in the operation and maintenance
cost of the PET radionuclide production facility that produces PET
radionuclides for use in producing radioactive drugs within the consortium for
noncommercial distributions among its associated members for medical use. The
PET radionuclide production facility within the consortium must be located at
an educational institution or a medical facility.

(36)
"Construction"
means the installation of foundations, or in-place assembly, erection,
fabrication, or testing for any structure, system, or component of a facility
or activity subject to the rules promulgated pursuant to Chapter 3748. of the
Revised Code that are related to radiological safety or security. The term
"construction" does not include:

(a)
Changes for
temporary use of the land for public recreational purposes;

(b)
Site
exploration, including necessary borings to determine foundation conditions or
other preconstruction monitoring to establish background information related to
the suitability of the site, the environmental impacts of construction or
operation, or the protection of environmental values;

(c)
Preparation of
the site for construction of the facility, including clearing of the site,
grading, installation of drainage, erosion and other environmental mitigation
measures, and construction of temporary roads and borrow areas;

(d)
Erection of
fences and other access control measures that are not related to the safe use
of, or security of, radiological materials subject to the rules promulgated
pursuant to Chapter 3748. of the Revised Code;

(f)
Erection of support buildings (e.g. construction
equipment storage sheds, warehouse and shop facilities, utilities, concrete
mixing plants, docking and unloading facilities, and office buildings) for use
in connection with the construction of the facility;

(40)
"Cyclotron" means
a particle accelerator in which the charged particles travel in an outward
spiral or circular path. A cyclotron accelerates charged particles at energies
usually in excess of ten megaelectron volts and is commonly used for production
of short half-life radionuclides for medical use.

(41)
"Declared pregnant woman" means a woman who has
voluntarily informed the licensee or registrant, in writing, of her pregnancy
and the estimated date of conception. The declaration remains in effect until
the declared pregnant woman withdraws the declaration in writing or is no
longer pregnant.

(42)
"Decommission"
means to safely remove any licensed operation from service and reduce residual
radioactivity to a level that permits release of the licensee's property for
unrestricted use and termination of the license. Termination of a license under
conditions other than unrestricted use is not permitted by Chapter 3748. of the
Revised Code.

(43)
"Dedicated check
source" means a radioactive source that is used to assure the consistent
performance of a radiation detection or measurement device over several months
or years.

(44)
"Deep dose
equivalent" or "Hd " applies to external whole body
exposure, and means the dose equivalent at a tissue depth of one centimeter,
one thousand milligram per square centimeter.

(45)
"Demand respirator" means an
atmosphere-supplying respirator that admits breathing air to the facepiece only
when a negative pressure is created inside the facepiece by
inhalation.

(46)
"Dentist" means an
individual licensed by the state of Ohio to practice dentistry under Chapter
4715. of the Revised Code.

(48)
"Depleted uranium"
means the source material uranium in which the isotope uranium-235 is less than
0.711 weight per cent of the total uranium present. Depleted uranium does not
include special nuclear material.

(49)
"Derived air concentration" or "DAC" means the
concentration of a given radionuclide in air which, if breathed by the
reference man for a working year of two thousand hours under conditions of
light work, results in an intake of one ALI. The condition of light work is
inhaling 1.2 cubic meters of air per hour for two thousand hours in a year. DAC
values are given in appendix C to rule
3701:1-38-12 of the
Administrative Code.

(50)
"Derived air concentration-hour or DAC-hour"
means the product of the concentration of radioactive material in air, which is
expressed as a fraction or multiple of the derived air concentration for each
radionuclide, and the time of exposure to that radionuclide, in hours. A
licensee or registrant may take two thousand DAC-hours to represent one ALI,
equivalent to a committed effective dose equivalent of 0.05 Sv (five
rem).

(51)
"Direct reading
dosimeter" means a device that measures radiation dose that does not require
another device to read the measured radiation dose. Examples of direct reading
dosimeters include pocket dosimeters and electronic dosimeters.

(52)
"Director" means the director of health or a
designee or authorized representative of the director.

(54)
"Discrete source"
means a radionuclide that has been processed so that its concentration within a
material has been purposely increased for use for commercial, medical, or
research activities.

(55)
"Disposable respirator" means a respirator for
which maintenance is not intended and that is designed to be discarded after
excessive breathing resistance, sorbent exhaustion, physical damage, or end-of
service-life renders it unsuitable for use. Examples of this type of respirator
are a disposable half-mask respirator or a disposable escape-only
self-contained breathing apparatus.

(56)
"Dose" or "radiation dose" is a generic term
that means absorbed dose, dose equivalent, effective dose equivalent, committed
effective dose equivalent, or total effective dose equivalent as defined in
other paragraphs of this rule.

(57)
"Dose equivalent" or "HT
" means the product of the absorbed dose in tissue, quality factor, and all
other necessary modifying factors at the location of interest. The units of
dose equivalent are the sievert and rem.

(58)
"Dose limits" or
"limits" means the permissible upper bounds of radiation doses established in
accordance with these regulations but excludes background radiation and medical
exposure.

(59)
"Dosimetry
processor" means a person that processes and evaluates individual monitoring
devices in order to determine the radiation dose delivered to the monitoring
devices.

(60)
"Effective dose
equivalent" or "HE " means the sum of the products of
the dose equivalent to each organ or tissue, HT, and the
weighting factor, WT, applicable to each of the body
organs or tissues that are irradiated: (HE =
SWT HT).

(61)
"Embryo" or "fetus" means the developing human
organism from conception until time of birth.

(62)
"Engineering controls" means mechanisms used to
protect health and minimize damage to life and property through engineering
specifications, design, and construction of the product or facility including
all of the security and safety features. This includes, but is not limited to,
auxiliary security and safety features such as additional external shielding,
barriers, and operational interlocks with associated processes.

(63)
"Entrance" or "access point" means any opening
through which an individual or extremity of an individual could gain access to
radiation areas or to licensed radioactive materials or registered radiation
generating equipment. This includes entry or exit portals of sufficient size to
permit human entry, irrespective of their intended use.

(64)
"Explosive material" means any chemical
compound, mixture or device which produces a substantial instantaneous release
of gas and heat spontaneously or by contact with sparks or flame.

(69)
"Facility" means
all buildings, equipment, structures and other stationary items that, in
addition to the meaning defined in division (H) of section
3748.01 of the Revised Code,
are:

(a)
Located on a single site or on
contiguous or adjacent sites and are operated by the same person and have
common corporate or business interests; or

(b)
Portions of a building or structure which
are operated by the same person and have common corporate or business
interests.

(70)
"Filtering facepiece" or "dust mask" means a
negative pressure particulate respirator with a filter as an integral part of
the facepiece or with the entire facepiece composed of the filtering medium,
not equipped with elastomeric sealing surfaces and adjustable straps.

(71)
"Fissile material" means the radionuclides
uranium-233, uranium-235, plutonium-239, and plutonium-241, or any combination
of these radionuclides. Fissile material means the fissile nuclides themselves,
not material containing fissile nuclides. Unirradiated natural uranium and
depleted uranium and natural uranium or depleted uranium that has been
irradiated in thermal reactors only, are not included in this definition.
Certain exclusions from fissile material controls are provided in rule
3701:1-50-13 of the
Administrative Code.

(72)
"Fit factor" means quantitative estimate of the
fit of a particular respirator to a specific individual, and typically
estimates the ratio of the concentration of a substance in ambient air to its
concentration inside the respirator when worn.

(73)
"Fit test" means the use of a protocol to
qualitatively or quantitatively evaluate the fit of a respirator on an
individual.

(74)
"Generally
applicable environmental radiation standards" means standards issued by the
United States environmental protection agency under the authority of the Atomic
Energy Act of 1954, as amended, that impose limits on radiation exposures or
levels, or concentrations or quantities of radioactive material, in the general
environment outside the boundaries of locations under the control of persons
possessing or using radioactive material.

(75)
"Gray" or "Gy" means the SI unit of absorbed
dose. One gray is equal to an absorbed dose of one joule per kilogram (one
hundred rads).

(76)
"Handler" means a
facility that handles sources of radiation unless possession is solely for the
purpose of transportation.

(77)
"Hazardous waste" means those wastes designated
as hazardous by rule
3745-51-03 of the Administrative
Code.

(78)
"Helmet" means a
rigid respiratory inlet covering that also provides head protection against
impact and penetration.

(79)
"High radiation area" means an area, accessible
to individuals, in which radiation levels from radiation sources external to
the body could result in an individual receiving a dose equivalent in excess of
one millisievert ( 0.1 rem) in one hour at thirty centimeters from the
radiation source or thirty centimeters from any surface that the radiation
penetrates.

(80)
"Hood" means a
respiratory inlet covering that completely covers the head and neck and may
also cover portions of the shoulders and torso.

(83)
"Individual monitoring devices" means devices
designed to be worn by a single individual for the assessment of dose
equivalent such as film badges; thermoluminescent dosimeters; optically
stimulated luminescent dosimeters; pocket ionization chambers; and personal air
sampling devices.

(84)
"Industrial
radiography" means the examination of the structure of materials by
nondestructive methods, utilizing sealed sources of radioactive material or
radiation-generating equipment.

(85)
"Internal dose" means that portion of the dose
equivalent received from radioactive material taken into the body.

(86)
"Irradiator" means a facility that uses
radioactive sealed sources for the irradiation of objects or materials and in
which radiation dose rates exceeding five grays (five hundred rads) per hour
exist at one meter from the sealed radioactive source in air or water, as
applicable for the irradiator type, but does not include irradiators in which
both the sealed source and the area subject to irradiation are contained within
a device and are not accessible to personnel.

(87)
"Lens dose equivalent" or "eye dose equivalent"
means the external exposure of the lens of the eye and is taken as the dose
equivalent at a tissue depth of 0.3 centimeters; i.e. three hundred milligrams
per square centimeter.

(88)
"License" means a license issued by the nuclear
regulatory commission, the director, or another agreement state in accordance
with rules adopted by those organizations.

(90)
"Licensed
activity" means an activity authorized by a radioactive material license which
is essential to achieving the purpose for which the license was issued or
amended.

(91)
"Licensed
material" means radioactive material received, possessed, used, transferred or
disposed of under a general or specific license.

(92)
"Loose-fitting facepiece" means a respiratory
inlet covering that is designed to form a partial seal with the face.

(93)
"Lost or missing licensed source of radiation"
means a licensed source of radiation whose location is unknown. It includes
material that has been shipped but has not reached its destination and whose
location cannot be readily traced in the transportation system.

(94)
"Low-level radioactive waste" or "LLRW," also
"low-level waste," or "LLW" means radioactive waste which is not high-level
radioactive waste, spent nuclear fuel, NARM, or byproduct material as defined
in section 11 E. (2) of the Atomic Energy Act of 1954, as amended, but is
radioactive material that the United States nuclear regulatory commission
classifies as low-level radioactive waste.

(95)
"Low specific activity material" or "LSA" means
radioactive material with limited specific activity which is nonfissile or is
excepted under rule
3701:1-50-13 of the
Administrative Code, and which satisfies the descriptions and limits set forth
below. Shielding materials surrounding the LSA material may not be considered
in determining the estimated average specific activity of the package contents.
LSA must be in one of three groups:

(i)
Uranium and thorium ores, concentrates
of uranium and thorium ores, and other ores containing naturally occurring
radioactive radionuclides which are not intended to be processed for the use of
these radionuclides;

(ii)
Solid
unirradiated natural uranium or depleted uranium or natural thorium or their
solid or liquid compounds or mixtures;

(iv)
Other radioactive material in which the
activity is distributed throughout and the estimated average specific activity
does not exceed thirty times the value for exempt material activity
concentration determined in accordance with rule
3701:1-50-25 of the
Administrative Code.

(i)
The radioactive material is distributed throughout a solid or a collection of
solid objects, or is essentially uniformly distributed in a solid compact
binding agent (such as concrete, bitumen, ceramic, etc.);

(ii)
The radioactive material is relatively
insoluble, or it is intrinsically contained in a relatively insoluble material,
so that even under loss of packaging, the loss of radioactive material per
package by leaching, when placed in water for seven days, would not exceed (
0.1 x A2 ); and

(iii)
The estimated average specific activity
of the solid does not exceed ( 0.002 x A2 ) per
gram.

(96)
"Management" means the chief executive officer
or other individual having the authority to manage, direct, or administer the
licensee's activities, or those persons' delegate or delegates.

(97)
"Medical institution" means an organization in
which more than one medical discipline is practiced.

(98)
"Medical use" means the intentional internal or
external administration of radioactive material or the radiation therefrom to
patients or human research subjects under the supervision of an authorized
user.

(99)
"Member of the
public" means any individual except when that individual is receiving an
occupational dose.

(101)
"Monitoring" or "radiation monitoring" or
"radiation protection monitoring" means the measurement of radiation levels,
concentrations, surface area concentrations or quantities of radioactive
material and the use of the results of these measurements to evaluate potential
exposures and doses.

(102)
"NARM" or "naturally occurring or
accelerator-produced radioactive material" means naturally occurring or
accelerator-produced radioactive material, including naturally occurring
material that is technologically enhanced, and those nuclides that are
generated in a charged particle accelerator, but does not include source
material, byproduct material, or special nuclear material.

(103)
"NARM licensing
state" means any state with regulations equivalent to the suggested state
regulations for control of radiation relating to, and an effective program for,
the regulatory control of NARM and which has been granted final designation by
the conference of radiation control program directors, inc.

(104)
"Nationally
tracked source" means a sealed source containing a quantity equal to or greater
than "Category 1" or "Category 2" levels of any radioactive material listed in
the appendix to rule
3701:1-38-25 of the
Administrative Code. In this context a sealed source is defined as radioactive
material that is sealed in a capsule or closely bonded, in a solid form and
which is not exempt from regulatory control. It does not mean material
encapsulated solely for disposal, or nuclear material contained in any fuel
assembly, subassembly, fuel rod, or fuel pellet. "Category 1" nationally
tracked sources are those containing radioactive material at a quantity equal
to or greater than the "Category 1" threshold. "Category 2" nationally tracked
sources are those containing radioactive material at a quantity equal to or
greater than the "Category 2" threshold but less than the "Category 1"
threshold.

(105)
"Negative
pressure respirator" or "tight fitting respirator" means a respirator in which
the air pressure inside the facepiece is negative during inhalation with
respect to the ambient air pressure outside the respirator.

(106)
"Nonstochastic
effect" or "deterministic effect" means health effects, the severity of which
varies with the dose and for which a threshold is believed to exist.
Radiation-induced cataract formation is an example of a nonstochastic
effect.

(107)
"NORM" or
"naturally occurring radioactive material" means any nuclide that is
radioactive in its natural physical state, but does not include source
material, byproduct material, or special nuclear material.

(108)
"Normal form
radioactive material" means radioactive material that has not been demonstrated
to qualify as special form radioactive material.

(109)
"Nuclear regulatory commission" means the
federal agency established by Title II of the Energy Reorganization Act of
1974, as amended, comprising the members of the commission and all offices,
employees, and representatives authorized to act in any case or matter related
to licensing and related regulatory function previously assigned to the AEC by
the Atomic Energy Act of 1954, as amended.

(110)
"Occupational dose" means the dose received by
an individual in the course of employment in which the individual's assigned
duties involve exposure to radiation or radioactive material from licensed and
unlicensed sources of radiation, whether in the possession of the licensee or
other person. Occupational dose does not include doses received from background
radiation, from any medical administration the individual has received, from
exposures to individuals administered radioactive materials and released in
accordance with rule
3701:1-58-30 of the
Administrative Code or equivalent United States nuclear regulatory commission
or agreement state regulations, from voluntary participation in medical
research programs, or as a member of the public.

(111)
"Package" means the packaging together with its
radioactive contents as presented for transport.

(b)
Type A package means
a type A packaging together with its radioactive contents. A type A package is
defined and must comply with the United States department of transportation
regulations in 49 C.F.R. 173 (as published in the October 1, 2005, Code of
Federal Regulations).

(c)
Type B
package means a type B packaging together with its radioactive contents. On
approval, a type B package design is designated by the United States nuclear
regulatory commission as B(U) unless the package has a maximum normal operating
pressure of more than seven hundred kilopascals (one hundred pounds per square
inch) gauge or a pressure relief device that would allow the release of
radioactive material to the environment under the tests specified in
10 C.F.R.
71.73 (hypothetical accident conditions) (as
published in the January 1, 2006, Code of Federal Regulations), in which case
it will receive a designation B(M). B(U) refers to the need for unilateral
approval of international shipments; B(M) refers to the need for multilateral
approval of international shipments. There is no distinction made in how
packages with these designations may be used in domestic transportation. To
determine their distinction for international transportation, see United States
department of transportation regulations in 49 C.F.R. 173 (as published in the
October 1, 2005 Code of Federal Regulations). A type B package approved before
September 6, 1983, was designated only as type B. Limitations on its use are
specified in 10 C.F.R.
71.19 (as published in the January 1, 2006,
Code of Federal Regulations).

(112)
"Packaging" means
the assembly of components necessary to ensure compliance with the packaging
requirements of rule 49 C.F.R. 173 Subpart I (as published in the October 1,
2005, Code of Federal Regulations). It may consist of one or more receptacles,
absorbent materials, spacing structures, thermal insulation, radiation
shielding, and devices for cooling or absorbing mechanical shocks. The vehicle,
tie-down system and auxiliary equipment may be designated as part of the
packaging.

(113)
"Particle
accelerator" means any machine capable of accelerating electrons, protons,
deuterons, or other charged particles in a vacuum and of discharging the
resultant particulate or other radiation into a medium at energies usually in
excess of one megaelectron volt. For purposes of this definition, "accelerator"
is an equivalent term.

(114)
"Person" means any individual, corporation,
association, business enterprise, or other legal entity either public or
private and any legal successor, representative, agent, or agency of that
individual, corporation, association, business enterprise, or other legal
entity. Person also includes the United States, states, political subdivisions
of states, and any department, agency, or instrumentality of the United States
or a state, except the U.S. department of energy or the U.S. nuclear regulatory
commission where the state regulation of radioactive material by either of
those agencies is prohibited by federal law.

(116)
"Pharmacist"
means a person who is licensed by the state of Ohio to practice pharmacy
pursuant to Chapter 4731. of the Revised Code.

(117)
"Physician" means a person who is licensed
pursuant to Chapter 4731. of the Revised Code to practice medicine or surgery
or osteopathic medicine or surgery.

(118)
"Planned special exposure" means an infrequent
exposure to radiation, separate from and in addition to the annual dose
limits.

(119)
"Podiatrist"
means an individual licensed by the state of Ohio to practice podiatry pursuant
to Chapter 4731. of the Revised Code.

(120)
"Positive pressure respirator" means a
respirator in which the pressure inside the respiratory inlet covering exceeds
the ambient air pressure outside the respirator.

(121)
"Positron Emission Tomography (PET) radionuclide
production facility" means a facility operating a cyclotron or accelerator for
the purpose of producing PET radionuclides.

(122)
"Powered air-purifying respirator" or "PAPR"
means an air-purifying respirator that uses a blower to force the ambient air
through air purifying elements to the inlet covering.

(123)
"Pressure demand
respirator" means a positive pressure atmosphere supplying respirator that
admits breathing air to the facepiece when the positive pressure is reduced
inside the facepiece by inhalation.

(124)
"Public dose" means the dose received by a
member of the public from exposure to radiation and/or radioactive material
released by the licensee, or to any other source of radiation under the control
of a licensee or registrant. Public dose does not include occupational dose or
doses received from background radiation, from any medical administration the
individual has received, from exposures to individuals administered radioactive
materials and released in accordance with rule
3701:1-58-30 of the
Administrative Code or equivalent United States nuclear regulatory commission
or agreement state regulations, or from voluntary participation in medical
research programs.

(125)
"Pyrophoric
material" means any liquid that ignites spontaneously in dry or moist air at or
below 54.4 degrees celsius (one hundred thirty degrees fahrenheit). A
pyrophoric solid is any solid material, other than one classed as an explosive,
which under normal conditions is liable to cause fires through friction,
retained heat from manufacturing or processing, or which can be ignited readily
and when ignited burns so vigorously and persistently as to create a serious
transportation, handling, or disposal hazard. Included are spontaneously
combustible and water-reactive materials.

(126)
"Qualitative fit test" or "QLFT" means a
pass/fail fit test to assess the adequacy of respirator fit that relies on the
individual's response to the test agent.

(127)
"Quality factor"
or "Q" means the modifying factor, as listed in paragraphs (A) and (B) of rule
3701:1-38-11 of the
Administrative Code, that is used to derive dose equivalent from absorbed
dose.

(128)
"Quantitative fit
test" or "QNFT" means an assessment of the adequacy of respirator fit by
numerically measuring the amount of leakage into the respirator.

(129)
"Quarter" or
"quarterly" means a period of time equal to one-fourth of the year observed by
the licensee or registrant, approximately thirteen consecutive weeks, providing
that the beginning of the first quarter in a year coincides with the starting
date of the year and that no day is omitted or duplicated in consecutive
quarters.

(130)
"Rad" means the
special unit of radiation absorbed dose. One rad is equal to an absorbed dose
of one hundred ergs per gram, or 0.01 joule per kilogram, or 0.01
gray.

(131)
"Radiation" or
"ionizing radiation" means alpha particles, beta particles, gamma rays, x-rays,
neutrons, high speed electrons, high speed protons, and other particles capable
of producing ions. Radiation does not include nonionizing radiation, such as
radio or microwaves, or visible, infrared or ultraviolet light.

(132)
"Radiation area"
means an area, accessible to individuals, in which radiation levels could
result in an individual receiving a dose equivalent in excess of 0.05
millisievert ( 0.005 rem) in one hour at thirty centimeters from the source of
radiation or from any surface that the radiation penetrates.

(133)
"Radiation-generating equipment" or "RGE" means any manufactured product or
device, or component of such a product or device, or any machine or system that
during operation can generate or emit radiation, except those that emit
radiation only from radioactive material. "Radiation-generating equipment" does
not include either of the following:

(b)
Microwave
ovens, including food service microwave ovens used for commercial and
industrial uses, television receivers, electric lamps, and other household
appliances and products that generate very low levels of radiation.

(134)
"Radiation Safety
Officer" or "RSO" means an individual designated by the licensee who has the
knowledge and responsibility for the overall radiation safety program at the
facility, to include the implementation of the daily radiation safety
operations and compliance with the rules.

(139)
"Reference man" means a hypothetical aggregation
of human physical and physiological characteristics arrived at by international
consensus. These characteristics may be used by researchers and public health
workers to standardize results of experiments and to relate biological insult
to a common base.

(140)
"Registrant"
means a person required by Chapter 3748. of the Revised Code to register
radiation-generating equipment with the director.

(141)
"Rem" means the special unit of any of the
quantities expressed as dose equivalent. The dose equivalent in rem is equal to
the absorbed dose in rads multiplied by the quality factor (one rem = 0.01
Sv).

(b)
The extension of investigative findings
and theories of a scientific or technical nature into practical application for
experimental and demonstration purposes, including the experimental production
and testing of models, devices, equipment, materials and processes. "Research
and development" does not include the internal or external administration of
sources of radiation to human beings.

(143)
"Residual radioactivity" means radioactivity in
structures, materials, soils, groundwater, and other media at a site resulting
from activities under the licensee's control. This includes radioactivity from
all licensed and unlicensed sources used by the licensee, but excludes
background radiation. It also includes radioactive materials remaining at the
site as a result of routine or accidental releases of radioactive material at
the site and previous burials at the site, even if those burials were made in
accordance with the provisions of 10 C.F.R. 20 (as published in the January 1,
2006, Code of Federal Regulations).

(144)
"Respiratory protective equipment or device"
means an apparatus, such as a respirator, used to reduce the individual's
intake of airborne radioactive materials.

(145)
"Restricted area" means an area access to which
is limited by the licensee or registrant for the purpose of protecting
individuals against undue risks from exposure to sources of radiation.
Restricted area does not include areas used as residential quarters, but
separate rooms in a residential building may be set apart as a restricted
area.

(146)
"Roentgen" means
the amount of gamma or x-rays required to produce ions resulting in a charge of
0.000258 coulombs per kilogram of air under standard conditions.

(147)
"Sanitary
sewerage" means a system of public sewers for carrying off wastewater and
refuse, but excluding sewage treatment facilities, septic tanks, and leach
fields owned or operated by the licensee.

(148)
"Sealed source" means radioactive material that
is encased in a manner designed to prevent leakage or escape of the radioactive
material.

(149)
"Sealed source
and device registry" means the national registry that contains all the
registration certificates, generated by both the United States nuclear
regulatory commission and the agreement states, that summarize the radiation
safety information for the sealed sources and devices and describe the
licensing and use conditions approved for the product.

(150)
"Seismic area"
means any area where the probability of a horizontal acceleration in rock of
more than 0.3 times the acceleration of gravity in two hundred fifty years is
greater than ten per cent, as designated by the United States geological
survey.

(151)
"Self-contained
breathing apparatus" or "SCBA" means an atmosphere-supplying respirator for
which the breathing air source is designed to be carried by the user.

(152)
"Shallow dose
equivalent" or "HS " means the external exposure of the
skin of the whole body or the skin of an extremity, is taken as the dose
equivalent at a tissue depth of 0.007 centimeter, or seven milligrams per
square centimeter.

(153)
"Sievert" or "Sv"
means the SI unit of any of the quantities expressed as dose equivalent. The
dose equivalent in sieverts is equal to the absorbed dose in grays multiplied
by the quality factor. One sievert equals one hundred rem.

(154)
"Site area
emergency" means events may occur, are in progress, or have occurred that could
lead to a significant release of radioactive material and that could require a
response by off-site response organizations to protect persons
off-site.

(155)
"Site boundary"
means that line beyond which the land or property is not owned, leased, or
otherwise controlled by the licensee or registrant.

(156)
"Site closure and stabilization" means those
actions that are taken upon completion of operations that prepare a disposal
site for custodial care and that assure that the disposal site will remain
stable and will not need ongoing active maintenance.

(157)
"Source material" means uranium, thorium, or any
combination thereof in any physical or chemical form, or any ores that contain
by weight at least one-twentieth of one per cent ( 0.05 per cent) of uranium,
thorium, or any combination thereof. Source material does not include special
nuclear material.

(159)
"Special form
radioactive material" means radioactive material that satisfies the following
conditions:

(a)
It is either a single solid
piece or is contained in a sealed capsule that can be opened only by destroying
the capsule;

(b)
The piece or
capsule has at least one dimension not less than five millimeters ( 0.2 inch);
and

(c)
It satisfies the test
requirements specified by the United States nuclear regulatory commission in
10 C.F.R.
71.75 (as published in the January 1, 2006,
Code of Federal Regulations). A special form encapsulation designed in
accordance with the United States nuclear regulatory commission requirements
identified in 10 C.F.R.
71.4, in effect on June 30, 1983, and
constructed prior to July 1, 1985, and a special form encapsulation designed in
accordance with the requirements of
10 C.F.R.
71.4 in effect on March 31, 1996, and
constructed before April 1, 1998, may continue to be used. Any other special
form encapsulation must meet the specifications of this definition.

(a)
Plutonium, uranium-233, uranium enriched in the isotope 233, or in the isotope
235, and any other material that the United States nuclear regulatory
commission determines to be special nuclear material, but does not include
source material pursuant to section 51 of the "Atomic Energy Act of 1954," 68
Stat 919, 42 USCA
2071.

(b)
Any material artificially enriched by any
of the foregoing but does not include source material.

(161)
"Special nuclear
material in quantities not sufficient to form a critical mass" means uranium
enriched in the isotope uranium-235 in quantities not exceeding three hundred
fifty grams of contained uranium-235; uranium-233 in quantities not exceeding
two hundred grams; plutonium in quantities not exceeding two hundred grams; or
any combination of them in accordance with the following formula: for each kind
of special nuclear material, determine the ratio between the quantity of that
special nuclear material and the quantity specified above for the same kind of
special nuclear material. The sum of such ratios for all of the kinds of
special nuclear material in combination shall not exceed unity.

(162)
"Stochastic
effect" means health effects that occur randomly and for which the probability
of the effect occurring, rather than its severity, is assumed to be a linear
function of dose without threshold. Hereditary effects and cancer incidence are
examples of stochastic effects.

(163)
"Supplied-air respirator" or "SAR" or "airline
respirator" means an atmosphere-supplying respirator for which the source of
breathing air is not designed to be carried by the user.

(164)
"Surface
contaminated object" or "SCO" means a solid object that is not itself classed
as radioactive material, but which has radioactive material distributed on any
of its surfaces. SCO must be in one of two groups with surface activity not
exceeding the following limits:

(i)
The non-fixed
contamination on the accessible surface averaged over three hundred square
centimeters, or the area of the surface if less than three hundred square
centimeters, does not exceed four becquerels per square centimeter
(10-4 microcurie per square centimeter) for beta and
gamma and low toxicity alpha emitters, or 0.4 becquerels per square centimeter
10-5 microcurie per square centimeter) for all other
alpha emitters;

(ii)
The fixed
contamination on the accessible surface averaged over three hundred square
centimeters, or the area of the surface if less than three hundred square
centimeters, does not exceed forty thousand becquerels per square centimeter
(one microcurie per square centimeter) for beta and gamma and low toxicity
alpha emitters, or four thousand becquerels per square centimeter ( 0.1
microcurie per square centimeter) for all other alpha emitters; and

(iii)
The non-fixed contamination plus the
fixed contamination on the inaccessible surface averaged over three hundred
square centimeters, or the area of the surface if less than three hundred
square centimeters, does not exceed forty thousand becquerels per square
centimeter (one microcurie per square centimeter) for beta and gamma and low
toxicity alpha emitters, or four thousand becquerels per square centimeter (
0.1 microcurie per square centimeter) for all other alpha emitters.

(b)
SCO-II: a solid object on
which the limits for SCO-I are exceeded and on which:

(i)
The non-fixed contamination on the
accessible surface averaged over three hundred square centimeters, or the area
of the surface if less than three hundred square centimeter, does not exceed
four hundred becquerels per square centimeter (10-2
microcurie per square centimeter) for beta and gamma and low toxicity alpha
emitters, or forty becquerels per square centimeter
(10-3 microcurie per square centimeter) for all
other alpha emitters;

(ii)
The
fixed contamination on the accessible surface averaged over three hundred
square centimeters, or the area of the surface if less than three hundred
square centimeters, does not exceed eight hundred thousand becquerels per
square centimeter (twenty microcuries per square centimeter) for beta and gamma
and low toxicity alpha emitters, or eighty thousand becquerels per square
centimeter (two microcuries per square centimeter) for all other alpha
emitters; and

(iii)
The non-fixed
contamination plus the fixed contamination on the inaccessible surface averaged
over three hundred square centimeters, or the area of the surface if less than
three hundred square centimeters, does not exceed eight hundred thousand
becquerels per square centimeter (twenty microcuries per square centimeter) for
beta and gamma and low toxicity alpha emitters, or eighty thousand becquerels
per square centimeter (two microcuries per square centimeter) for all other
alpha emitters.

(165)
"Survey" means an evaluation of the radiological
conditions and potential hazards incident to the production, use, transfer,
release, disposal or presence of radioactive material or other sources of
radiation. When appropriate, such an evaluation includes a physical survey of
the location of radioactive material, or the sources of radiation and
measurements or calculations of levels of radiation, or concentrations or
quantities of radioactive material present.

(166)
"Tight-fitting facepiece" means a respiratory
inlet covering that forms a complete seal with the face.

(168)
"Transport index"
means the dimensionless number, rounded up to the next tenth, placed on the
label of a package, to designate the degree of control to be exercised by the
carrier during transportation. The transport index is the number determined by
multiplying the maximum radiation level in millisievert per hour at one meter (
3.3 feet) from the external surface of the package by one hundred, which is
equivalent to the maximum radiation level in millirem per hour at one meter (
3.3 feet).

(169)
"Type A quantity"
means a quantity of radioactive material, the aggregate radioactivity of which
does not exceed A1 for special form radioactive
material, or A2 for normal form radioactive material,
where A1 and A2 are given in rule
3701:1-50-25 of the
Administrative Code.

(170)
"Type B quantity" means a quantity of
radioactive material greater than a type A quantity.

(172)
"United States
department of energy" means the department of energy established by the
Department of Energy Organization Act, PL 95-91, August 4, 1977, 91 Stat. 565,
42 U.S.C.
7101 et seq., to the extent that the
department of energy or its duly authorized representatives, exercises
functions formerly vested in the United States atomic energy commission, its
chairman, members, officers and components and transferred to the United States
energy research and development administration and to the administrator thereof
pursuant to Sections 104(b), (c) and (d) of the Energy Reorganization Act of
1974 ( PL 93-438, 88 Stat. 1233 at 1237,
42 U.S.C.
5814 ) and retransferred to the secretary of
energy pursuant to Section 301(a) of the Department of Energy Organization Act
( PL 95-91, 91 Stat. 565 at 577-578,
42 U.S.C.
7151 ).

(173)
"Unrestricted area" or "uncontrolled area" means
any area, access to which is neither restricted nor controlled by the licensee
or registrant.

(175)
"Very high
radiation area" means an area, accessible to individuals, in which radiation
levels from radiation sources external to the body could result in an
individual receiving an absorbed dose in excess of five gray (five hundred rad)
in one hour at one meter from a source of radiation or from any surface that
the radiation penetrates. At very high doses received at high dose rates, units
of absorbed dose, gray and rad, are appropriate, rather than units of dose
equivalent, sievert and rem.

(176)
"Veterinarian" means an individual licensed by
the state of Ohio to practice veterinary medicine pursuant to Chapter 4741. of
the Revised Code.

(177)
"Waste" means
those low-level radioactive wastes containing source, special nuclear, or
byproduct material that are acceptable for disposal in a land disposal
facility. For the purposes of this definition, low-level radioactive waste
means radioactive waste not classified as high-level radioactive waste,
transuranic waste, spent nuclear fuel, or byproduct material as defined in
paragraph (A)(26)(b) of this rule, or byproduct material as defined in section
11 E. (3) and (4) of the Atomic Energy Act of 1954, as amended.

(179)
"Weighting factor - WT "
for an organ or tissue, (T), is the proportion of the risk of stochastic
effects resulting from irradiation of that organ or tissue to the total risk of
stochastic effects when the whole body is irradiated uniformly. For calculating
the effective dose equivalent, the values of WT are:

T

Organ dose weighting factors

Organ or tissue

WT

Gonads

0.25

Breast

0.15

Red bone marrow

0.12

Lung

0.12

Thyroid

0.03

Bone surfaces

0.03

Remainder

0.30a

Whole body

1.00b

\a\0.30 results from 0.06 for each
of five "remainder" organs, excluding the skin and the lens of the eye, that
receive the highest doses.

\b\ for the purpose of weighting the
external whole body dose (for adding it to the internal dose) a single
weighting factor, WT = 1.0, has been specified. The use
of other weighting factors for external exposure will be approved on a
case-by-case basis until such time as specific guidance is issued.

(181)
"Worker" means an individual engaged in
activities licensed or registered by the department and controlled by a
licensee or registrant, but does not include the licensee or
registrant.

(182)
"Working level"
or "WL" means any combination of short-lived radon decay products (for
radon-222: polonium-218, lead-214, bismuth-214, and polonium-214; and for
radon-220: polonium-216, lead-212, bismuth-212, and polonium-212) in one liter
of air that will result in the ultimate emission of 1.3 x
105 million electron volts alpha particle
energy.

(183)
"Working level
month" or "WLM" means a cumulative exposure to one working level for one
hundred seventy hours. (Two thousand working hours per year/twelve months per
year equals approximately one hundred seventy hours per month.)

(184)
"Year" means the
period of time beginning in January used to determine compliance with the
provisions of this rule. The licensee or registrant may change the starting
date of the year used to determine compliance by the licensee or registrant
provided that the change is made at the beginning of the year and that no day
is omitted or duplicated in consecutive years.

(B)
The terms set out in paragraph (A) of
this rule may be redefined in other chapters as promulgated pursuant to Chapter
3748. of the Revised Code as used in that chapter only.